OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-03-01 to 2024-03-01.)

Article	Citations
The Influence of Radiation on Confinement Properties of Nuclear Waste Glasses	23
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel	20
Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods	16
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core	15
Emission of Noble Gases Binary Mixtures under Excitation by the Products of the ⁶Li (n, α)³ H Nuclear Reaction	12
Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network	11
A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System	10
Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification	9
Effect of Thickness and Compaction Degree of Overburden Soil on Radon Reduction for Uranium Tailings Reservoir	8
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing	7
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	6
Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations	6
Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations	6
Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel	5
Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis	5
Transient Study on the HTR-PM with TINTE-vPower Coupling Code Package	5
Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method	4
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	4
An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors	4
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	4
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas	4
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	4
Bubble Bursting and Drainage Characteristics at the Free Surface of a Liquid Pool with an Aerosol	4
RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4

A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants	4
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	4
Remaining Useful Life Prediction Techniques of Electric Valves for Nuclear Power Plants with Convolution Kernel and LSTM	4
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	4
Monte Carlo Simulation and Experimental Validation for Radiation Protection with Multiple Complex Source Terms and Deep Penetration for a Radioactive Liquid Waste Cementation Facility	4
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	3
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library	3
A Novel and High-Precision Method for Calculating the γ-Ray Build-Up Factor for Multilayer Shields	3
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant	3
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	3
Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident	3
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel	3
Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System	3
The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME	3
Development and Validation of Rapid 3D Radiation Field Evaluation Technique for Nuclear Power Plants	3
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response	3
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	3
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	3
The Investigation on Heat Transfer Characteristics of Steam Condensation in Presence of Noncondensable Gas under Natural Convection	2
Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments	2
Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy	2
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System	2
Nonlinear Seismic Response Characteristics of CAP1400 Nuclear Island Structure on Soft Rock Sites	2
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	2
Single-Vehicle Transportation Security System of Radioactive Materials Based on Group Relationship to Prevent Loss and Theft	2
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube	2
Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1	2
Numerical Investigation of Water Film Evaporation with the Countercurrent Air in the Asymmetric Heating Rectangular Channel for Passive Containment Cooling System	2
Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model	2
Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code	2
Uranium Decontamination from Waste Soils by Chlorination with ZrCl4 in LiCl-KCl Eutectic Salt	2
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride	2
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	2
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	2
Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART	2
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions	2
Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault	2
Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor	2
Vehicle Transport Security System Based on the Self-Security Intelligence of Radioactive Material	2
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis	2
Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000	2
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	2
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models	2
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	2
Theoretical Study on the Characteristics of Critical Heat Flux in Rectangular Channel of Natural Circulation under Motion Conditions	2
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	2
Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code	1
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	1
Modelling and Validation of CANDU Shim Operation Using Coupled TRACE/PARCS with Regulating System Response	1
Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography	1

Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction	1
Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program	1
Research and Implementation of SVDU Simulator Based on Emulation Technology	1
Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident	1
Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements	1
Study of the Design and Assembly of a High Harmonic Fast Wave Antenna for an LAPD	1
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	1
Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility	1
Detection of Illegal Movement in Radioactive Material Transportation Security Systems	1
Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques	1
Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM	1
Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants	1
Electrochemical Deposition of U and RE Elements Using the Stirred Liquid Cadmium Cathode in LiCl-KCl Molten Salts	1
Dynamic Simulation of a Warship Control Valve Based on a Mechanical-Electric-Fluid Cosimulation Model	1
Electrochemical Removal of Rare Earth Element in LiCl-KCl Molten Salt	1
Inerting Strategy for a Demonstration-Scale Hot Cell Facility Based on Experiences from Pilot-Scale Argon Cell Facility Operation and CFD Analysis	1
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management	1
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1
Lognormal-Based Sampling for Fission Product Yields Uncertainty Propagation in Pebble-Bed HTGR	1
Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt	1
Cracking Driving Force at the Tip of SCC under Heterogeneous Material Mechanics Model of Safe-End Dissimilar Metal-Welded Joints in PWR	1
Development of Fuel Product Barrier Monitoring System Based on State Functions in State-Oriented Emergency Operating Procedure	1
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
Methodology for Establishing Segmentation Strategy for Large Metal Components from Nuclear Power Plants with Consideration of Packaging into Containers	1
Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code	1
Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident	1
Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants	1
Study on Release and Migration of Radionuclides under the Small Break Loss of Coolant Accident in a Marine Reactor	1
A Digital Controller for Reactivity Monitoring and Power Control	1
Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor	1
Effect of Deposit on the Evaporation Rate of Adhered Salt in Uranium Dendrite	1
Numerical Study of Unsteady Pressure Fluctuation at Impeller Outlet of a Centrifugal Pump	1
The Study of Three-Dimensional Granular Stream Flowing through the Test Hopper-Shaped Target	1
Integrated Security System (ISS) Design and Evaluation for Commercial Nuclear Power Plant	1
Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1
Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance	1
Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code	1
Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks	1
Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock-Up at KAERI	1